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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20239A2701998-09-0202 September 1998
Summary of 980813 Meeting W/Ceco in Rockville,Md Re Brpnp Defueled TSs & Defueled Emergency Plan W/Associated Exemption.List of Meeting Attendees & Brpnp Meeting Handout Encl
ML20236K9471998-07-0606 July 1998
Summary of 980625 Drop in Visit by Plant Representatives to Discuss CPC 980302 Response to NRC Request for Info, .Representatives Considering Submittal of Suppl Info Re Emergency Preparedness Plan & Defueled TSs
ML20202E6601997-11-25025 November 1997
Summary of 971029 Meeting W/Big Rock Point in Rockville,Md Re Proposed Amend of TS to Reflect Permanent Shutdown & Defueled Condition of Plant & Proposed Exemption from 10CFR50 Emergency Planning Requirements
ML20058K5821993-12-0909 December 1993
Summary of 931130 Meeting W/Util in Rockville,Md Re Decommissioning Plan for Plant.Attendees Listed in Encl
ML20059H9201993-11-0303 November 1993
Summary of 931025 Meeting W/Util in Rockville,Md Re end-of- License Issues for Plant.List of Meeting Attendees & Licensee Material Handouts Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20057E5831993-09-10010 September 1993
Summary of Operating Reactors Events Meeting 93-33 on 930901
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20248F3141989-10-0202 October 1989
Summary of 890907 Meeting W/Util Re Simulator Facility Plans for Plant,Per 10CFR55.45(b).List of Attendees Encl
ML20244D3371989-06-12012 June 1989
Summary of 890509 Meeting W/Util Re Simulator Facility Plans.List of Meeting Attendees & Viewgraphs Encl
IA-92-231, Summary of 881021 Meeting W/Cpc at Plant Re Licensee Masoneilan Valve Parts 10CFR21 Rept1988-11-0303 November 1988
Summary of 881021 Meeting W/Cpc at Plant Re Licensee Masoneilan Valve Parts 10CFR21 Rept
ML20128C6761988-11-0303 November 1988
Summary of 881021 Meeting W/Cpc at Plant Re Licensee Masoneilan Valve Parts 10CFR21 Rept
ML20149L4981988-02-12012 February 1988
Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline Encl
ML20236A9731987-10-13013 October 1987
Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl
ML20207T2011987-03-17017 March 1987
Summary of 870303 & 04 Meetings W/Util Re Environ Qualification of safety-related Electrical Equipment Cables. Attendees List Encl
ML20211P1361986-07-16016 July 1986
Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl
ML20141G6101986-04-16016 April 1986
Summary of 860331 Meeting W/Util & BNL in Bethesda,Md Re 10CFR50,App R Issues.List of Attendees Encl
ML20153H2251986-02-18018 February 1986
Summary of 860128-31 Meetings W/Util at Facility Re in-progress Audit of Facility Dcrdr to Clarify Certain Aspects of Process & to Confirm That Review Conducted Appropriately.List of Attendees Encl
ML20054L9051982-06-30030 June 1982
Summary of 820628 Meeting W/Util in Bethesda,Md Re Min Shift Staffing at Facility & Use of Probabilistic Risk Assessment in Licensing Activities.Attendee List & Handouts Encl
ML20147F9131978-12-15015 December 1978
Summary of 781116 Meeting W/Util to Discuss SEP Review of Site Geology & Geotechnical Data.List of Attendees Encl
ML20148G7781978-01-18018 January 1978
Summary of 780105 Meeting W/Util Re SEP Review of Environ Qualification of Electrical Equipment
ML20126E5641976-04-0808 April 1976
Summary of 760318-19 Meeting W/Util & NUS Corp in Charlevoix,Mi Re Review of ECCS Performance.Attendee List & Generic Info Request Re ECCS Review in Electrical, Instrumentation & Control Areas Encl
ML20126E5171974-01-0909 January 1974
Summary of 731205 Meeting W/Util,Mcpherson Associates & Suntac Nuclear in Bethesda,Md Re Seismic Design,Pipe & Vessel Code,Instrumentation,Redundancy & Reliability Requirements for Proposed Autodepressurization Sys
ML20126E5211973-11-20020 November 1973
Notification of 731205 Meeting W/Util in Bethesda,Md to Discuss Scope of Plant Mods to Permit Autodepressurization. Refs Util 730724 Preliminary Description of Reactor Depressurization Sys
1998-09-02
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20239A2701998-09-0202 September 1998
Summary of 980813 Meeting W/Ceco in Rockville,Md Re Brpnp Defueled TSs & Defueled Emergency Plan W/Associated Exemption.List of Meeting Attendees & Brpnp Meeting Handout Encl
ML20202E6601997-11-25025 November 1997
Summary of 971029 Meeting W/Big Rock Point in Rockville,Md Re Proposed Amend of TS to Reflect Permanent Shutdown & Defueled Condition of Plant & Proposed Exemption from 10CFR50 Emergency Planning Requirements
ML20058K5821993-12-0909 December 1993
Summary of 931130 Meeting W/Util in Rockville,Md Re Decommissioning Plan for Plant.Attendees Listed in Encl
ML20059H9201993-11-0303 November 1993
Summary of 931025 Meeting W/Util in Rockville,Md Re end-of- License Issues for Plant.List of Meeting Attendees & Licensee Material Handouts Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20057E5831993-09-10010 September 1993
Summary of Operating Reactors Events Meeting 93-33 on 930901
ML20217C5121991-07-0303 July 1991
Summary of Operating Reactors Events Meeting 91-12 on 910626
ML20248F3141989-10-0202 October 1989
Summary of 890907 Meeting W/Util Re Simulator Facility Plans for Plant,Per 10CFR55.45(b).List of Attendees Encl
ML20244D3371989-06-12012 June 1989
Summary of 890509 Meeting W/Util Re Simulator Facility Plans.List of Meeting Attendees & Viewgraphs Encl
IA-92-231, Summary of 881021 Meeting W/Cpc at Plant Re Licensee Masoneilan Valve Parts 10CFR21 Rept1988-11-0303 November 1988
Summary of 881021 Meeting W/Cpc at Plant Re Licensee Masoneilan Valve Parts 10CFR21 Rept
ML20128C6761988-11-0303 November 1988
Summary of 881021 Meeting W/Cpc at Plant Re Licensee Masoneilan Valve Parts 10CFR21 Rept
ML20149L4981988-02-12012 February 1988
Summary of 871207 Meeting W/Utils in Bethesda,Md Re Licensees Revised Proposal to Comply W/Nrc Requirement for Simulation Facilities Under 10CFR55.45(b).List of Attendees & Util Simulation Facility Group Guideline Encl
ML20236A9731987-10-13013 October 1987
Summary of 870915-16 Meetings W/Four Facility Licensees in Bethesda,Md Re Proposal to Apply for NRC Approval for Simulation Facilities.Viewgraphs & Related Documents Encl
ML20207T2011987-03-17017 March 1987
Summary of 870303 & 04 Meetings W/Util Re Environ Qualification of safety-related Electrical Equipment Cables. Attendees List Encl
ML20211P1361986-07-16016 July 1986
Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl
ML20141G6101986-04-16016 April 1986
Summary of 860331 Meeting W/Util & BNL in Bethesda,Md Re 10CFR50,App R Issues.List of Attendees Encl
ML20153H2251986-02-18018 February 1986
Summary of 860128-31 Meetings W/Util at Facility Re in-progress Audit of Facility Dcrdr to Clarify Certain Aspects of Process & to Confirm That Review Conducted Appropriately.List of Attendees Encl
ML20054L9051982-06-30030 June 1982
Summary of 820628 Meeting W/Util in Bethesda,Md Re Min Shift Staffing at Facility & Use of Probabilistic Risk Assessment in Licensing Activities.Attendee List & Handouts Encl
ML20147F9131978-12-15015 December 1978
Summary of 781116 Meeting W/Util to Discuss SEP Review of Site Geology & Geotechnical Data.List of Attendees Encl
ML20148G7781978-01-18018 January 1978
Summary of 780105 Meeting W/Util Re SEP Review of Environ Qualification of Electrical Equipment
ML20126E5641976-04-0808 April 1976
Summary of 760318-19 Meeting W/Util & NUS Corp in Charlevoix,Mi Re Review of ECCS Performance.Attendee List & Generic Info Request Re ECCS Review in Electrical, Instrumentation & Control Areas Encl
ML20126E5171974-01-0909 January 1974
Summary of 731205 Meeting W/Util,Mcpherson Associates & Suntac Nuclear in Bethesda,Md Re Seismic Design,Pipe & Vessel Code,Instrumentation,Redundancy & Reliability Requirements for Proposed Autodepressurization Sys
ML20126E5211973-11-20020 November 1973
Notification of 731205 Meeting W/Util in Bethesda,Md to Discuss Scope of Plant Mods to Permit Autodepressurization. Refs Util 730724 Preliminary Description of Reactor Depressurization Sys
1998-09-02
[Table view] |
Text
_ _ _ _ _
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'. DOCKET E0; 50-155 I LICENSfE: Consumers Power Company r i
FACILITYa Big Rock Point l MINUTES OF MEETING WIT 11 COMSUMERS POWER COMPANY Or MICHIGAN REGARDING
! THE ADDITION OF AUTO-DEPRESSION CAPABILITY TO THE BIG ROCK PODTI PIET I
Representatives of Consumers Power Company and the AEC (see attachment)-
- l met in Bethesda on December 5,1973, to discuss seismic design, pipe
! and vessel code, instrumentation, redundancy, and reliability require-
! ments for the reactor auto-depressurization system proposed for Big l Rock Point. Reference was made to previous Consumer Power Company i submittals; I
l 1. Special Report No.15 " Preliminary Description of Reactor
! Depressurization System", July 19, 1973, submitted to AEC by l CPCo letter dated July 24, 1973.
I 2. " Big Rock Point Loss of Coolant Analysis with Automatic Depres-aurization and NFS Demonstration Fuel submitted to AEC by letter dated September 22, 1972.
It was emphasized by CPCo that the system is designed so that no single failure will actuate or prevent actuation of the system and that a two-
- minute delay after receipt of the auto-depressurization actuation signal >
- is necessary to allow personnel evacuation of the containment structure
! before the reactor vessel is depressurized to contai-nt.
, ! A quench tank containing cold water about equal to the primary coolant I
i water volume is provided to quench steam released unintentionally from one relief valve. During auto-depressurisation, quenching would occur for about 40 seconds after which the primary system steam would no
- longer be condensed and would pass through the heated quench tank water it 'to the containment structure. Accidental opening of one relief valve, M with failure to isolate, could activate the entire biswdown system (3
_' ' ar 4 relief valves of approximately 800,000 lbs/hr flow capacity each at 1350 psi) when lov level steam drum and reactor vessel signals are received coincidentally since auto-depressurisation is activated due to loss of water by level signals' from the steam drum and reactor vessel.
The need for further evaluation of manual operation and isolation @
capability was indicated.
!. S l O &o 502M
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- Seismic design criteria for the proposed modifications are based on j ., review of earthquakes that have been recorded for the area and otatistical i T, considerations. De new T connection for the relief valve header to
, . g. be installed in the 12 'nch steam line will not be hydrostatically y tested but will be 100% radiographed. The quench tank, although not required during auto-depressurization, is designed not to fail during
'. accident conditions to avoid the dar. age potential resulting from the i
release of the tank water. The significant change discussed during the meeting involved the decision to use a small quench tank, as discussed above, instead of the spent fuel pool water with the result j that containment pressurization is greater than originally planned using spent fuel water-steam suppression but less than DBA LOCA pres-
- surization that has been previously evaluated.
Component delivery schedules, according to CPCo, smy not be consistent with completion of the modification to conform with the interfan
, Acceptance ECCS Criteria by July 1974.
A final design report is expected during January 1974.
James J. Shea Operating Reactors Branch #2 Directorate of Licensing Enclosure.
l List of Attendees l cc w/ enclosure:
M. Sewell, CPCo AEC PDK L I:aading RP Reading E. G. Case A. Gianbusso R. S. Boyd RP/TR Assistant Directors i I
RP/TR Branch Chiefs I
i w T. J. Carter it J. M. Hendrie 75 J. J. Shea
~
J. Scinto D. Nelson i
ACR3 (16)
K. Kanur I
,,,,,,R. Pollard L:0RB f2 L -L :DRB /
II. Bernreuter - X7403 -- --
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. . . , , JJShea- h,_ ,,R_ --
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o.v e +- 1. 4. _1/2/14 1/I/74 l F$rm AEC 318 (Rev. 9 53) AECM O240 spo caa se e s sea-s sao. sea l 4
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'B LIST OF ATTE.NDEES- - -
V
.N,_ans Aff1,liatfo_n, D. DeMoor Consunars Power Company F. Mscri Consumers Power Company J. Rang Consuraers Power Company R. Sewell Consumers Power Cospany l
J. Henry McPherson Associates Inc.
D. Wilder Suntac Nuclear F. Hueliner Suntac Nuclear J. Shea AEC - Licensing K. Kapur AEC - Licensing R. Po31ard AEC - Licensing D. Bernreuter AEC - Licensing i
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&,s OPrats > _ , , ,
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Foran AEC SIS (Rev. 9 5)) AICM 0240 ePo ces es s e me s-, sea-see
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